CN117194873A - Parameter calibration method and device for LOCA monitoring system of reactor - Google Patents
Parameter calibration method and device for LOCA monitoring system of reactor Download PDFInfo
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Abstract
The application relates to a method for calibrating parameters of a reactor LOCA monitoring system, which comprises the following steps of 101, selecting a reference cycle of a reactor; 102, calculating a proportionality coefficient B of LOCA monitoring system parameters calibrated by a current cycle and a reference cycle of a reactor; and 103, calculating LOCA monitoring system parameters of the current cycle calibration of the reactor according to the proportionality coefficient B. The application also relates to a reactor LOCA monitoring system parameter calibration device, computer equipment and a storage medium. The application realizes the calibration of the LOCA monitoring system parameters in the stage from the power rising to 75% full power after the current cycle of refueling of the reactor, so that the LOCA monitoring system can accurately monitor the power distribution state in the reactor core from the power rising to 75% full power after the major repair of the reactor is completed, and the safe and stable operation of the pressurized water reactor is ensured.
Description
Technical Field
The application relates to the technical field of nuclear measuring instruments outside a nuclear power station reactor, in particular to a nuclear pressure water reactor LOCA monitoring system parameter calibration method, a device, computer equipment and a storage medium.
Background
The reactor LOCA (loss of coolant accident, coolant loss accident) monitoring system is mainly used for 1000MWe pressurized water reactors. The reactor LOCA monitoring system is used for recalculating the three-dimensional distribution condition of the power inside the reactor core through collecting real-time current data measured by a power range detector outside the reactor core and a corresponding mathematical physical model formula, and displaying the result as calculated values such as a reactor core running state graph, a pressurized water reactor linear power density, a LOCA safety margin, an axial power deviation, a quadrant power inclination and the like. The values calculated during normal operation of the reactor must remain within sufficient margins and remain within certain limits, as specified by the reactor operation. These limits ensure that the safety-related restrictions of the fuel cladding are met in the event of a LOCA accident for the reactor assembly, in order to reduce the probability of fuel breakage under the accident conditions or to reduce the damage caused by fuel breakage under the accident conditions.
To ensure the accuracy of the reconstructed calculation of the LOCA monitoring system of the reactor, the parameters of the LOCA monitoring system need to be updated periodically. During normal power operation, parameters of the LOCA monitoring system need to be modified every month to calibrate calculation of the LOCA monitoring system, and the calculated value of the LOCA monitoring system is ensured to be within an error range. After the reactor unit is subjected to shutdown overhaul, due to the influences of loading changes and burnup changes of the reactor core fuel assemblies, parameters calibrated through tests in the LOCA monitoring system before shutdown are not suitable for working conditions after shutdown overhaul, and proper LOCA monitoring system parameters are required to be reset, so that the calculated value of the LOCA monitoring system is ensured to be within an error range.
The current reactor is at the stage of increasing power to 75% full power after the current cycle of refueling, and the LOCA monitoring system parameter is the last test measurement value of the last cycle, so that the numerical error calculated by the LOCA monitoring system is larger, and the safe and stable operation of the pressurized water reactor unit is not facilitated.
Disclosure of Invention
Based on the above, it is necessary to provide a method, a device, a computer device and a storage medium for calibrating the parameters of the LOCA monitoring system of the reactor in the stage of increasing the power to 75% of full power after the current cycle of refueling, so that the LOCA monitoring system can accurately monitor the power distribution state in the reactor core after the major repair of the reactor to the stage of increasing the power to 75% of full power, thereby ensuring the safe and stable operation of the pressurized water reactor.
In order to solve the problems, the application provides a method for calibrating parameters of a reactor LOCA monitoring system, which comprises the following steps:
step 101, selecting a reference cycle of a reactor;
102, calculating a proportionality coefficient B of LOCA monitoring system parameters calibrated by a current cycle and a reference cycle of a reactor;
and 103, calculating LOCA monitoring system parameters of the current cycle calibration of the reactor according to the proportionality coefficient B.
Further, in step 101, a history cycle of the reactor is selected as a reference cycle of the reactor, wherein the history cycle of the reactor is from the last history overhaul of the reactor to the next history overhaul of the reactor; the current cycle of the reactor is from the current overhaul to the next overhaul after the current overhaul and the reloading of the reactor;
the reference cycle of the reactor is chosen according to the following principle:
the reactor core loading modes of the reactor in the reference cycle and the current cycle are consistent, and the position of the power range detector outside the reactor core is not replaced;
the reactor at least completes calibration of LOCA monitoring system parameters through a test at least once in the power-up stage after the reference cycle overhaul refueling;
the calibrated LOCA monitoring system parameters include a neutron transmission proportionality coefficient T and a neutron detector sensitivity coefficient S.
Further, the reactor is a pressurized water reactor, and the pressurized water reactor core loading mode comprises a checkerboard mode, an OUT-IN mode and a modified OUT-IN mode; the chessboard mode is that new and old fuel assemblies are arranged IN a staggered mode, the OUT-IN mode is that more new fuel assemblies are arranged at the periphery of the reactor core, and the OUT-IN mode is that more new fuel assemblies are arranged IN a sandwich layer between the center of the reactor core and the periphery of the reactor core.
Further, step 102 includes the steps of:
step 1021, calculating the reactor core power distribution of the reactor in the power rising stage after the current cycle and the reference cycle overhaul refueling respectively;
step 1022, respectively calculating response coefficients of each fuel assembly of the reactor to the corresponding reactor core external power range detector in the power-up stage after the major repair and the refueling of the reference cycle and the current cycle;
step 1023, calculating the proportionality coefficient B of LOCA monitoring system parameters calibrated by the current cycle and the reference cycle of the reactor according to the reactor core power distribution of the reactor in the power-up stage after the current cycle and the reference cycle major repair and the response coefficient of each fuel assembly to the corresponding reactor core external power range detector.
Further, in step 1021, the core of the reactor is divided according to four quadrants, the fuel assemblies in the four quadrants are symmetrically arranged, and the fuel assemblies in the four quadrants are symmetrically arranged; in the same cycle, the relative power of the fuel assemblies at the same location within the four quadrant core is the same;
reactor core power distribution in power-up stage after current cycle overhaul refueling is the relative power P of i-position fuel assemblies in one quadrant reactor core in power-up stage after current cycle overhaul refueling i ′；
Calculating the relative power P of the fuel assembly at the i position in one quadrant core of the reactor in the power increasing stage after the current cycle overhaul refueling by utilizing a three-dimensional core calculation program i ′；
Reactor core power distribution at power-up stage after refueling of reference cycle is given by relative power P of i-position fuel assemblies in one quadrant reactor core of reactor at power-up stage after refueling of reference cycle i ；
Relative power P of i-position fuel assembly in one quadrant reactor core in power-up stage after reference cycle overhaul refueling i The method is obtained through experimental measurement of the reactor in the power-up stage after the reference cycle overhaul refueling;
i is a fuel assembly position serial number in a quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in the quadrant reactor core;
and (3) taking a power platform of the reference cycle through test calibration LOCA monitoring system parameter as a power platform of reactor core power distribution after major repair and refueling of the current cycle and the reference cycle.
Further, in step 1022, an off-stack power range detector is correspondingly provided for a fuel assembly in one quadrant core, and the off-stack power range detectors of the four quadrant cores are symmetrically arranged;
in the same cycle, the response coefficients of the fuel assemblies at the same position in the four quadrant reactor cores to the corresponding off-stack power range detectors are the same; the response coefficients of the fuel assemblies of the reactor at the same position in the reference cycle and the current cycle are the same for the corresponding off-stack power range detectors;
the response coefficient of each fuel assembly corresponding to the detector of the power range outside the reactor in the power raising stage after the heavy repair and the refueling of the reference cycle and the current cycle of the reactor is the response coefficient A of the pressurized water reactor corresponding to the detector of the power range outside the reactor in the i position of the fuel assembly in one quadrant reactor core in the power raising stage after the heavy repair and the refueling of the reference cycle or the current cycle i ；
Calculation of pressurized water reactor on reference cycle or time using Monte Carlo procedureResponse coefficient A of i-position fuel assembly corresponding to power range detector of reactor in one quadrant reactor core in power rising stage after pre-cycle overhaul and refueling i ；
i is a fuel assembly position serial number in a quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in the quadrant reactor core;
taking a power platform of reactor core power distribution after the current cycle and the reference cycle overhaul and refueling as a response coefficient A of the reactor after the current cycle and the reference cycle overhaul and refueling i Is a power platform of (a).
Further, in step 1023, a scaling factor B is calculated according to the following formula;
wherein i is a position serial number of fuel assemblies in one quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in one quadrant reactor core;
P′ i the relative power of the fuel assembly at the i position in a quadrant reactor core in the power increasing stage after the current cycle overhaul refueling for the pressurized water reactor;
P i the relative power of the fuel assembly at the i position in a quadrant reactor core in the power increasing stage after the major repair and the refueling of the reference cycle is carried out for the pressurized water reactor;
A i and (3) the response coefficient of the fuel assembly at the i position in the quadrant reactor core corresponding to the off-stack power range detector in the power-up stage of the pressurized water reactor after the major repair of the reference cycle or the current cycle.
Further, in step 103, the LOCA monitoring system parameters calibrated by the test in the power-up stage after the reference cycle overhaul and the refueling of the reactor are proportionally adjusted by using the scaling factor B to obtain the LOCA monitoring system parameters calibrated in the power-up stage after the current cycle and the refueling of the reactor:
S’＝B×S
T’＝T
s is the sensitivity coefficient of the neutron detector calibrated in a reference cycle of the reactor; s' is the sensitivity coefficient of the neutron detector calibrated in the current cycle of the reactor; t is a neutron transmission proportionality coefficient calibrated in a reference cycle of the reactor; t' is the neutron transmission proportionality coefficient of the reactor calibrated in the current cycle.
In order to solve the above problems, the present application further provides a parameter calibration device for a LOCA monitoring system of a reactor, including:
a selection module 201 for selecting a reference cycle of the reactor;
a first calculation module 202, configured to calculate a scaling factor B of LOCA monitoring system parameters calibrated by a current cycle and a reference cycle of the reactor;
the second calculation module 203 is configured to calculate a LOCA monitoring system parameter of the current cycle calibration of the reactor according to the scaling factor B;
the data connection among the selection module 201, the first calculation module 202 and the second calculation module 203.
In order to solve the technical problems, the application provides a computer device, which comprises a memory and a processor, wherein the memory is stored with computer readable instructions, and the processor realizes the steps of the reactor LOCA monitoring system parameter calibration method when executing the computer readable instructions.
In order to solve the technical problem, the application provides a computer readable storage medium, wherein computer readable instructions are stored on the computer readable storage medium, and the steps of the reactor LOCA monitoring system parameter calibration method are realized when the computer readable instructions are executed.
The beneficial technical effects of the application are as follows:
according to the method, the device, the computer equipment and the storage medium for calibrating the parameters of the LOCA monitoring system of the reactor, the calibration of the parameters of the LOCA monitoring system in the stage of increasing the power to 75% of full power after the current cycle of the pressurized water reactor is used for refueling, the calculation accuracy of the LOCA monitoring system in the stage of increasing the power to 75% of full power after the current cycle of the reactor is used for overhauling and refueling is improved, the frequency of false alarm of the LOCA monitoring system in the stage of increasing the power to 75% of full power after the current cycle of the reactor is greatly reduced, and therefore the time of processing the false alarm of the LOCA monitoring system in the stage of increasing the power after the current cycle of the reactor is used for overhauling and refueling is greatly reduced, and the power generation efficiency of the pressurized water reactor is improved.
Drawings
FIG. 1 is a flow chart of one embodiment of a reactor LOCA monitoring system parameter calibration method of the present application;
FIG. 2 is a schematic structural view of one embodiment of a reactor LOCA monitoring system parameter calibration device of the present application.
FIG. 3 is a schematic structural view of one embodiment of a computer device of the present application.
Detailed Description
Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs; the terminology used in the description of the application herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the application; the terms "comprising" and "having" and any variations thereof, in the description of the application and the claims and the description of the drawings above, are intended to cover a non-exclusive inclusion. The terms first, second and the like in the description and in the claims or in the above-described figures, are used for distinguishing between different objects and not necessarily for describing a sequential or chronological order.
Reference herein to "an embodiment" means that a particular feature, structure, or characteristic described in connection with the embodiment may be included in at least one embodiment of the application. The appearances of such phrases in various places in the specification are not necessarily all referring to the same embodiment, nor are separate or alternative embodiments mutually exclusive of other embodiments. Those of skill in the art will explicitly and implicitly appreciate that the embodiments described herein may be combined with other embodiments.
The technical solutions of the present application will be clearly and completely described below with reference to the accompanying drawings and specific embodiments.
Referring to FIG. 1, a flow chart of one embodiment of a reactor LOCA monitoring system parameter calibration method is shown, comprising the steps of:
step 101, selecting a reference cycle of a reactor;
102, calculating a proportionality coefficient B of LOCA monitoring system parameters calibrated by a current cycle and a reference cycle of a reactor;
and 103, calculating LOCA monitoring system parameters of the current cycle calibration of the reactor according to the proportionality coefficient B.
In this embodiment, in step 101, a history cycle of the reactor is selected as a reference cycle of the reactor, where the history cycle of the reactor is from a last history overhaul of the reactor to a next history overhaul of the reactor; the current cycle of the reactor is from the current overhaul to the next overhaul after the current overhaul and the reloading of the reactor;
the reference cycle of the reactor is chosen according to the following principle:
the reactor core loading modes of the reactor in the reference cycle and the current cycle are consistent, and the position of the power range detector outside the reactor core is not replaced;
the reactor at least completes calibration of LOCA monitoring system parameters through a test at least once in the power-up stage after the reference cycle overhaul refueling;
the calibrated LOCA monitoring system parameters include a neutron transmission proportionality coefficient T and a neutron detector sensitivity coefficient S.
IN this embodiment, the reactor is a pressurized water reactor, and the pressurized water reactor core loading mode includes a checkerboard mode, an OUT-IN mode, and a modified OUT-IN mode; the chessboard mode is that new and old fuel assemblies are arranged IN a staggered mode, the OUT-IN mode is that more new fuel assemblies are arranged at the periphery of the reactor core, and the OUT-IN mode is that more new fuel assemblies are arranged IN a sandwich layer between the center of the reactor core and the periphery of the reactor core.
In this embodiment, step 102 includes the following steps:
step 1021, calculating the reactor core power distribution of the reactor in the power rising stage after the current cycle and the reference cycle overhaul refueling respectively;
step 1022, respectively calculating response coefficients of each fuel assembly of the reactor to the corresponding reactor core external power range detector in the power-up stage after the major repair and the refueling of the reference cycle and the current cycle;
step 1023, calculating the proportionality coefficient B of LOCA monitoring system parameters calibrated by the current cycle and the reference cycle of the reactor according to the reactor core power distribution of the reactor in the power-up stage after the current cycle and the reference cycle major repair and the response coefficient of each fuel assembly to the corresponding reactor core external power range detector.
In this embodiment, in step 1021, the core of the reactor is divided according to four quadrants, the fuel assemblies in the four quadrants are symmetrically arranged, and the fuel assemblies in the four quadrants are symmetrically arranged; in the same cycle, the relative power of the fuel assemblies at the same location within the four quadrant core is the same;
the reactor core power distribution of the reactor in the power-boosting stage after the current cycle overhaul refueling is the relative power P 'of the fuel assemblies at the i position in the one quadrant reactor core in the power-boosting stage after the current cycle overhaul refueling' i ；
Calculating the relative power P 'of the fuel assembly at the i position in one quadrant core of the reactor in the power increasing stage after the current cycle overhaul refueling by utilizing a three-dimensional core calculation program' i ；
Reactor core power distribution at power-up stage after refueling of reference cycle is given by relative power P of i-position fuel assemblies in one quadrant reactor core of reactor at power-up stage after refueling of reference cycle i ；
Relative power P of i-position fuel assembly in one quadrant reactor core in power-up stage after reference cycle overhaul refueling i The method is obtained through experimental measurement of the reactor in the power-up stage after the reference cycle overhaul refueling;
i is a fuel assembly position serial number in a quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in the quadrant reactor core;
and (3) taking a power platform of the reference cycle through test calibration LOCA monitoring system parameter as a power platform of reactor core power distribution after major repair and refueling of the current cycle and the reference cycle.
In this embodiment, in step 1022, an off-stack power range detector is correspondingly provided for one fuel assembly in one quadrant core, and the off-stack power range detectors of the four quadrant cores are symmetrically arranged with each other;
in the same cycle, the response coefficients of the fuel assemblies at the same position in the four quadrant reactor cores to the corresponding off-stack power range detectors are the same; the response coefficients of the fuel assemblies of the reactor at the same position in the reference cycle and the current cycle are the same for the corresponding off-stack power range detectors;
the response coefficient of each fuel assembly corresponding to the detector of the power range outside the reactor in the power raising stage after the heavy repair and the refueling of the reference cycle and the current cycle of the reactor is the response coefficient A of the pressurized water reactor corresponding to the detector of the power range outside the reactor in the i position of the fuel assembly in one quadrant reactor core in the power raising stage after the heavy repair and the refueling of the reference cycle or the current cycle i ；
Calculating response coefficient A of a corresponding reactor power range detector of an i-position fuel assembly in a quadrant reactor core in a power increasing stage of a pressurized water reactor after major repair and refueling in a reference cycle or a current cycle by using a Monte Carlo program i ；
i is a fuel assembly position serial number in a quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in the quadrant reactor core;
taking a power platform of reactor core power distribution after the current cycle and the reference cycle overhaul and refueling as a response coefficient A of the reactor after the current cycle and the reference cycle overhaul and refueling i Is a power platform of (a).
In this embodiment, in step 1023, the scaling factor B is calculated according to the following formula;
wherein i is a position serial number of fuel assemblies in one quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in one quadrant reactor core;
P′ i the relative power of the fuel assembly at the i position in a quadrant reactor core in the power increasing stage after the current cycle overhaul refueling for the pressurized water reactor;
P i the relative power of the fuel assembly at the i position in a quadrant reactor core in the power increasing stage after the major repair and the refueling of the reference cycle is carried out for the pressurized water reactor;
A i and (3) the response coefficient of the fuel assembly at the i position in the quadrant reactor core corresponding to the off-stack power range detector in the power-up stage of the pressurized water reactor after the major repair of the reference cycle or the current cycle.
In this embodiment, in step 103, the LOCA monitoring system parameters calibrated by the test in the power-up stage after the major repair and the refueling of the reference cycle of the reactor are proportionally adjusted by using the scaling factor B to obtain the LOCA monitoring system parameters calibrated in the power-up stage after the current cycle of the reactor:
S’＝B×S
T’＝T
s is the sensitivity coefficient of the neutron detector calibrated in a reference cycle of the reactor; s' is the sensitivity coefficient of the neutron detector calibrated in the current cycle of the reactor; t is a neutron transmission proportionality coefficient calibrated in a reference cycle of the reactor; t' is the neutron transmission proportionality coefficient of the reactor calibrated in the current cycle.
The method for calibrating the LOCA monitoring system parameters of the reactor, provided by the embodiment, realizes the calibration of the LOCA monitoring system parameters in the stage of increasing the power to 75% of full power after the current cycle refueling of the reactor; the LOCA monitoring system parameters calculated by the application are consistent with the LOCA monitoring system parameters calibrated by the test on the 75% full power platform, which shows that the LOCA monitoring system can monitor the power distribution situation of the reactor core more accurately in the 0% -75% full power interval, and ensure the safe operation of the reactor under the design of safety analysis; according to the LOCA monitoring system parameter calculated by the application, the LOCA monitoring system does not generate the warning of excessive reactor linear power density, excessive LOCA safety margin, excessive axial power deviation and excessive quadrant power inclination in the stage of increasing power to 75% of full power after the current cycle of the reactor is subjected to overhaul and reloading, so that the time of processing the false warning of the LOCA monitoring system in the stage of increasing power after the current cycle of the reactor is greatly reduced, and the power generation efficiency of the pressurized water reactor is improved.
Referring to fig. 2, as an implementation of the method, the present application provides an embodiment of a LOCA monitoring system parameter calibration device for a reactor, where the embodiment of the device corresponds to the embodiment of the LOCA monitoring system parameter calibration method for a reactor, and the device can be applied to various electronic devices specifically.
The reactor LOCA monitoring system parameter calibration device according to the embodiment includes:
a selection module 201 for selecting a reference cycle of the reactor;
a first calculation module 202, configured to calculate a scaling factor B of LOCA monitoring system parameters calibrated by a current cycle and a reference cycle of the reactor;
the second calculation module 203 is configured to calculate a LOCA monitoring system parameter of the current cycle calibration of the reactor according to the scaling factor B;
the selecting module, the first calculating module and the second calculating module are in data connection.
The LOCA monitoring system parameter calibration device for the reactor provided by the embodiment realizes the calibration of LOCA monitoring system parameters in the stage of increasing power to 75% full power after the current cycle refueling of the reactor; the LOCA monitoring system parameters calculated by the application are consistent with the LOCA monitoring system parameters calibrated by the test on the 75% full power platform, which shows that the LOCA monitoring system can monitor the power distribution situation of the reactor core more accurately in the 0% -75% full power interval, and ensure the safe operation of the reactor under the design of safety analysis; according to the LOCA monitoring system parameter calculated by the application, the LOCA monitoring system does not generate the warning of excessive reactor linear power density, excessive LOCA safety margin, excessive axial power deviation and excessive quadrant power inclination in the stage of increasing power to 75% of full power after the current cycle of the reactor is subjected to overhaul and reloading, so that the time of processing the false warning of the LOCA monitoring system in the stage of increasing power after the current cycle of the reactor is greatly reduced, and the power generation efficiency of the pressurized water reactor is improved.
As an implementation of the above method, the present application provides an embodiment of a computer device, which corresponds to the embodiment of the above method for calibrating a LOCA monitoring system parameter of a reactor.
The computer device of the present embodiment includes a memory 301, a processor 302, and a network interface 303 that are communicatively connected to each other through a system bus. It should be noted that only computer devices having components 301-303 are shown in the figures, but it should be understood that not all of the illustrated components are required to be implemented and that more or fewer components may be implemented instead. It will be appreciated by those skilled in the art that the computer device herein is a device capable of automatically performing numerical calculations and/or information processing according to predetermined or stored instructions, and the hardware thereof includes, but is not limited to, microprocessors, application specific integrated circuits, programmable gate arrays, digital processors, embedded devices, and the like.
The computer equipment can be a desktop computer, a notebook computer, a palm computer, a cloud server and other computing equipment. The computer equipment can perform man-machine interaction with a user through a keyboard, a mouse, a remote controller, a touch pad or voice control equipment and the like.
The memory 301 comprises at least one type of readable storage medium including flash memory, hard disk, multimedia card, card memory, random access memory, static random access memory, read only memory, electrically erasable programmable read only memory, magnetic disk, optical disk, and the like. In some embodiments, the memory 301 may be an internal storage unit of the computer device, such as a hard disk or a memory of the computer device. In other embodiments, the memory 301 may also be an external storage device of the computer device, such as a plug-in hard disk, a smart memory card, a secure digital card, a flash memory card, etc. that is provided on the computer device. Of course, the memory 301 may also include both an internal memory unit of the computer device and an external memory device. In this embodiment, the memory 301 is typically used to store an operating system and various application software installed on the computer device, such as computer readable instructions of the above method. In addition, the memory 301 may be used to temporarily store various types of data that have been output or are to be output.
The processor 302 may be a central processing unit, controller, microcontroller, microprocessor, or other data processing chip in some embodiments. The processor 302 is typically used to control the overall operation of the computer device. In this embodiment, the processor 302 is configured to execute computer readable instructions or process data stored in the memory 301, for example, computer readable instructions for executing the above-mentioned LOCA monitoring system parameter calibration method.
The network interface 303 may include a wireless network interface or a wired network interface, which network interface 303 is typically used to establish communication connections between the computer device and other electronic devices.
The computer equipment provided by the embodiment realizes the calibration of LOCA monitoring system parameters in the stage of increasing power to 75% full power after the current cycle of the reactor is reloaded; the LOCA monitoring system parameters calculated by the application are consistent with the LOCA monitoring system parameters calibrated by the test on the 75% full power platform, which shows that the LOCA monitoring system can monitor the power distribution situation of the reactor core more accurately in the 0% -75% full power interval, and ensure the safe operation of the reactor under the design of safety analysis; according to the LOCA monitoring system parameter calculated by the application, the LOCA monitoring system does not generate the warning of excessive reactor linear power density, excessive LOCA safety margin, excessive axial power deviation and excessive quadrant power inclination in the stage of increasing power to 75% of full power after the current cycle of the reactor is subjected to overhaul and reloading, so that the time of processing the false warning of the LOCA monitoring system in the stage of increasing power after the current cycle of the reactor is greatly reduced, and the power generation efficiency of the pressurized water reactor is improved.
As an implementation of the above method, the present application provides an embodiment of a computer readable storage medium, which corresponds to the embodiment of the above method for calibrating a reactor LOCA monitoring system parameter.
The computer readable storage medium according to the present embodiment stores computer readable instructions executable by at least one processor to cause the at least one processor to perform the steps of the reactor LOCA monitoring system parameter calibration method as described above.
The computer readable storage medium provided by the embodiment realizes the calibration of LOCA monitoring system parameters in the stage of increasing power to 75% full power after the current cycle of the reactor is reloaded; the LOCA monitoring system parameters calculated by the application are consistent with the LOCA monitoring system parameters calibrated by the test on the 75% full power platform, which shows that the LOCA monitoring system can monitor the power distribution situation of the reactor core more accurately in the 0% -75% full power interval, and ensure the safe operation of the reactor under the design of safety analysis; according to the LOCA monitoring system parameter calculated by the application, the LOCA monitoring system does not generate the warning of excessive reactor linear power density, excessive LOCA safety margin, excessive axial power deviation and excessive quadrant power inclination in the stage of increasing power to 75% of full power after the current cycle of the reactor is subjected to overhaul and reloading, so that the time of processing the false warning of the LOCA monitoring system in the stage of increasing power after the current cycle of the reactor is greatly reduced, and the power generation efficiency of the pressurized water reactor is improved.
The foregoing examples illustrate only a few embodiments of the application and are described in detail herein without thereby limiting the scope of the application. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the application, which are all within the scope of the application. Accordingly, the scope of protection of the present application is to be determined by the appended claims.
Claims (10)
1. A method for calibrating parameters of a LOCA monitoring system of a reactor, comprising the steps of:
step 101, selecting a reference cycle of a reactor;
102, calculating a proportionality coefficient B of LOCA monitoring system parameters calibrated by a current cycle and a reference cycle of a reactor;
and 103, calculating LOCA monitoring system parameters of the current cycle calibration of the reactor according to the proportionality coefficient B.
2. The method for calibrating parameters of LOCA monitoring system according to claim 1, wherein in step 101, a history cycle of the reactor is selected as a reference cycle of the reactor, and the history cycle of the reactor is from a last history overhaul of the reactor to a next history overhaul of the reactor; the current cycle of the reactor is from the current overhaul to the next overhaul after the current overhaul and the reloading of the reactor;
the reference cycle of the reactor is chosen according to the following principle:
the reactor core loading modes of the reactor in the reference cycle and the current cycle are consistent, and the position of the power range detector outside the reactor core is not replaced;
the reactor at least completes calibration of LOCA monitoring system parameters through a test at least once in the power-up stage after the reference cycle overhaul refueling;
the calibrated LOCA monitoring system parameters include a neutron transmission proportionality coefficient T and a neutron detector sensitivity coefficient S.
3. The method for reactor LOCA monitoring system parameter calibration according to claim 1, wherein step 102 includes the steps of:
step 1021, calculating the reactor core power distribution of the reactor in the power rising stage after the current cycle and the reference cycle overhaul refueling respectively;
step 1022, respectively calculating response coefficients of each fuel assembly of the reactor to the corresponding reactor core external power range detector in the power-up stage after the major repair and the refueling of the reference cycle and the current cycle;
step 1023, calculating the proportionality coefficient B of LOCA monitoring system parameters calibrated by the current cycle and the reference cycle of the reactor according to the reactor core power distribution of the reactor in the power-up stage after the current cycle and the reference cycle major repair and the response coefficient of each fuel assembly to the corresponding reactor core external power range detector.
4. The method for calibrating a LOCA monitoring system parameter of a reactor according to claim 3, wherein in step 1021, the core of the reactor is divided into four quadrants, fuel assemblies in the four quadrants are symmetrically arranged, and fuel assemblies in the four quadrants are symmetrically arranged, wherein the fuel assemblies in the four quadrants are the same position; in the same cycle, the relative power of the fuel assemblies at the same location within the four quadrant core is the same;
reactor core power distribution in power-up stage after current cycle overhaul refueling is the relative power P of i-position fuel assemblies in one quadrant reactor core in power-up stage after current cycle overhaul refueling i ′；
Calculating the relative power P of the fuel assembly at the i position in one quadrant core of the reactor in the power increasing stage after the current cycle overhaul refueling by utilizing a three-dimensional core calculation program i ′；
Reactor core power distribution at power-up stage after refueling of reference cycle is given by relative power P of i-position fuel assemblies in one quadrant reactor core of reactor at power-up stage after refueling of reference cycle i ；
Relative power P of i-position fuel assembly in one quadrant reactor core in power-up stage after reference cycle overhaul refueling i The method is obtained through experimental measurement of the reactor in the power-up stage after the reference cycle overhaul refueling;
i is a fuel assembly position serial number in a quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in the quadrant reactor core;
and (3) taking a power platform of the reference cycle through test calibration LOCA monitoring system parameter as a power platform of reactor core power distribution after major repair and refueling of the current cycle and the reference cycle.
5. The method for calibrating parameters of LOCA monitoring system in a reactor according to claim 3, wherein in step 1022, an off-stack power range detector is correspondingly arranged in one fuel assembly in one quadrant core, and the off-stack power range detectors of the four quadrant cores are symmetrically arranged;
in the same cycle, the response coefficients of the fuel assemblies at the same position in the four quadrant reactor cores to the corresponding off-stack power range detectors are the same; the response coefficients of the fuel assemblies of the reactor at the same position in the reference cycle and the current cycle are the same for the corresponding off-stack power range detectors;
the response coefficient of each fuel assembly corresponding to the detector of the power range outside the reactor in the power raising stage after the heavy repair and the refueling of the reference cycle and the current cycle of the reactor is the response coefficient A of the pressurized water reactor corresponding to the detector of the power range outside the reactor in the i position of the fuel assembly in one quadrant reactor core in the power raising stage after the heavy repair and the refueling of the reference cycle or the current cycle i ；
Calculating response coefficient A of a corresponding reactor power range detector of an i-position fuel assembly in a quadrant reactor core in a power increasing stage of a pressurized water reactor after major repair and refueling in a reference cycle or a current cycle by using a Monte Carlo program i ；
i is a fuel assembly position serial number in a quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in the quadrant reactor core;
taking a power platform of reactor core power distribution after the current cycle and the reference cycle overhaul and refueling as a response coefficient A of the reactor after the current cycle and the reference cycle overhaul and refueling i Is a power platform of (a).
6. A method for calibrating parameters of a LOCA monitoring system according to claim 3, wherein in step 1023, the proportionality coefficient B is calculated according to the following formula;
wherein i is a position serial number of fuel assemblies in one quadrant reactor core, i is a natural number with a value of 1-j, and j is the total number of all fuel assemblies in one quadrant reactor core;
P i ' is the relative power of the fuel assembly at the i position in the quadrant reactor core of the pressurized water reactor in the power increasing stage after the current cycle overhaul refueling;
P i the relative power of the fuel assembly at the i position in a quadrant reactor core in the power increasing stage after the major repair and the refueling of the reference cycle is carried out for the pressurized water reactor;
A i and (3) the response coefficient of the fuel assembly at the i position in the quadrant reactor core corresponding to the off-stack power range detector in the power-up stage of the pressurized water reactor after the major repair of the reference cycle or the current cycle.
7. The method for calibrating LOCA monitoring system parameters of a reactor according to claim 1, wherein in step 103, scaling the LOCA monitoring system parameters calibrated by the test in the power-up stage after the reference cycle overhaul refueling by using the scaling factor B is used to obtain the LOCA monitoring system parameters calibrated by the reactor in the power-up stage after the current cycle refueling:
S’＝B×S
T’＝T
s is the sensitivity coefficient of the neutron detector calibrated in a reference cycle of the reactor; s' is the sensitivity coefficient of the neutron detector calibrated in the current cycle of the reactor; t is a neutron transmission proportionality coefficient calibrated in a reference cycle of the reactor; t' is the neutron transmission proportionality coefficient of the reactor calibrated in the current cycle.
8. A reactor LOCA monitoring system parameter calibration device, comprising:
a selection module 201 for selecting a reference cycle of the reactor;
a first calculation module 202, configured to calculate a scaling factor B of LOCA monitoring system parameters calibrated by a current cycle and a reference cycle of the reactor;
the second calculation module 203 is configured to calculate a LOCA monitoring system parameter of the current cycle calibration of the reactor according to the scaling factor B;
the data connection among the selection module 201, the first calculation module 202 and the second calculation module 203.
9. A computer device comprising a memory and a processor, the memory having stored thereon computer readable instructions, wherein the processor, when executing the computer readable instructions, performs the steps of the reactor LOCA monitoring system parameter calibration method as claimed in any one of claims 1-7.
10. A computer readable storage medium having computer readable instructions stored thereon, wherein the computer readable instructions when executed implement the steps of the reactor LOCA monitoring system parameter calibration method as recited in any one of claims 1-7.
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